05000282/LER-1980-015-01, /01T-0:on 800429,containment Maint Airlock Showed Leakage Greater than Tech Spec Limit.Caused by Degradation of Airlock Door Seal.Inner Door Seals Replaced & Leak Tested Satisfactorily

From kanterella
(Redirected from ML19323C630)
Jump to navigation Jump to search
/01T-0:on 800429,containment Maint Airlock Showed Leakage Greater than Tech Spec Limit.Caused by Degradation of Airlock Door Seal.Inner Door Seals Replaced & Leak Tested Satisfactorily
ML19323C630
Person / Time
Site: Prairie Island 
Issue date: 05/13/1980
From: Hunstad A
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19323C624 List:
References
LER-80-015-01T-01, LER-80-15-1T-1, NUDOCS 8005160409
Download: ML19323C630 (2)


LER-1980-015, /01T-0:on 800429,containment Maint Airlock Showed Leakage Greater than Tech Spec Limit.Caused by Degradation of Airlock Door Seal.Inner Door Seals Replaced & Leak Tested Satisfactorily
Event date:
Report date:
2821980015R01 - NRC Website

text

.

CRC FORM 384 U.E. NUCLEAR RE!tfLATORY COMMISS40N (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

lh (PLEASE PRINT OR TYPE ALL REQUIRED t*lFORMATION)

I 6

lo l1l lM l N l P l Il Nl 1lg0 l0 l -l 0l 0 l 0 l 0 l 0 l - l 0 l 0lg 4 l 1 l 1 l 1 l 1 lgl l

lg 7

8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T

$Ou$"C dl 0l Sl 0l 0l012 l 8 l 2 @l Ol 4l 2l 9l8 l0 $l0 l 5 l 1l 3l 8l 0l@

0 1 7

8 60 61 DOCKET NUM8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O 2 lA vninmotric test of the containment maintenance airlock showed leakage of about l

10131 1600 sccm vs. the Tech Soec limit of 409 secm.

After replacement of the inner door 1 0 4 Innn1c-chn lonknen mon enrod t.rns nhout R cccm.

The outer door was operable through-l i

10 I S I i nne eso novina wch snnc A_A.A s.c nnnlina.

Nn offect on nublic health and I

o s Isafety.

I 10171 1 1

101811 l

80 F

8 9 DE CODE

$ 8C E COMPONENT CODE SUS OD'E SU E

l Sl Alh Wh Wh lP l E l N l El TlR l@ ]@ { @

O 9 7

8 9

10 11 12 13 18 19 20 SEQUE NTI AL OCCURRENCE REPORT REVISION LER EVENT YE AR REPORT NO.

CODE TYPE NO.

O,ajog,RO I810l L--J 10 11 IsI Ld I ol 11 LT]

L--J LoJ

_ 21 22 23 24 26 2F M

29 30 31 32.

T K N A O

ON PL NT M

HOURS S8 IT FOR 8.

SU L R MANUF CTURER LLJ@La_l@

L7J@

L2.l@

loIoIoIol LJ.J@

LN_j@

lAl@

lC l3l1l0lh 33 34 3S 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1 O I p,.n,. m a,,,. n (con neenchnA ennninmoneal vnnnrl_T l

1 1 l

I i 2 I

I mi 1

i 4 I

I 7

8 9 80

$A S

% POWER OTHER STA rUS dis O RY DISCOVERY DESCRIPTION W W @ l1l0l0l@l NA l

[ Bj@l Surveillance test.

l ACTIVITY CO TENT

- OuNT O, ACTivlTv @ l LOCATION CF RREME @

REuASED OPRufASE h

NA l

NA l

1 6 7

N 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

I nln In l@Lz.J@l "i I

1 2 ERSO~NEL iN;U4ES DESCR,niO~ @

~UM8ER l 0l0 l0 l@l NA l

i a F

8 9 11 12 80 LOSS OP OR OAMAGE TO FACILITY Q TYPE

DESCRIPTION

v

[. Zj@l NA l

i 9 7

a 9 10 80 ISSUE

DESCRIPTION

[p_jhl NA l

lllllllllllll5 2 O 7

8 9 to 68 69 80 A A Hunstad NAME OF PREPARER PHONE:

c p ostsoos

~

y

=

May 13, 1980 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 Licensee Event Report 80-015 Supplemental Report Cause Description and Corrective Actions (contd.)

The volumetric test pressurizes the space between the doors. Thus, the test pressure tends to open the inner door. Also, door stops are installed prior to the test to pre-vent overcompression of (and damage to) the door seals. For these reasons it is concluded that door leakage would probably have been acceptable during the postulated accident.

However, this was not proved.

On May 1 a volumetric test of the personnel airlock also showed unacceptable results.

The same procedure was used for this test.

The procedure was then changed to perform the test without door stops and the measured leakage was zero.

The test procedure will be modified.

i 1

l